CN101846535A - Method for measuring steam-water mismatching amount of steam generator - Google Patents
Method for measuring steam-water mismatching amount of steam generator Download PDFInfo
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- CN101846535A CN101846535A CN200910119390A CN200910119390A CN101846535A CN 101846535 A CN101846535 A CN 101846535A CN 200910119390 A CN200910119390 A CN 200910119390A CN 200910119390 A CN200910119390 A CN 200910119390A CN 101846535 A CN101846535 A CN 101846535A
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Abstract
The invention discloses a method for measuring the steam-water mismatching amount of a steam generator for a nuclear power station, which comprises the following steps of: (1) measuring water supply temperature TFW and water supply flow mFWM of water entering the steam generator to obtain actual flow mFW; (2) determining thermal power PW required by converting the water into steam; (3) determining thermal power PS generated by a loop of a reactor; and (4) determining steam-water mismatching amount (PW-PS). In the method, the actual water supply flow of the steam generator is corrected, and the steam-water mismatching amount of the flow is changed into the thermal power mismatching amount, so that the problem of inaccurate flow measurement caused by the change of temperature and pressure of the steam is solved fundamentally, the measurement error is reduced, and the safety and reliability of the nuclear power station are improved. The actual operation of the integral measuring method only needs the accurate measurement of the water supply flow mFWM and the water supply temperature TFW, and thus the method has the advantages of few required measurement parameters, convenient operation and high accuracy and feasibility.
Description
Technical field
The present invention relates to a kind of Steam-water Flow measuring method, be specifically related to the measuring method of used in nuclear power station steam-water mismatching amount of steam generator.
Background technology
The nuclear power station steam generator water mismatching amount of steam is the very important parameter of the control of nuclear power safety, and the measuring method that the nuclear power station steam generator water mismatching amount of steam is commonly used is at present: at first, measure the actual confluent of steam generator.Then, measure the steam generator steam flow.Deduct the latter with the former more at last and obtain water mismatching amount of steam.Because the pressure in the steam generator changes often, cause the steam generator steam flow deviation that records bigger, make the water mismatching amount of steam that obtains at last have than large deviation, thus the action of false triggering equipment.
Summary of the invention
The measuring method that the purpose of this invention is to provide a kind of steam-water mismatching amount of steam generator, this method is converted to the energy amount of mismatch with the Steam-water Flow amount of mismatch, has improved the safe shape and the reliability of nuclear power station.
Realize the technical scheme of the object of the invention: a kind of measuring method of steam-water mismatching amount of steam generator comprises set by step following: (1) measures the feed temperature T that enters steam generator
FWWith feedwater flow m
FWM, obtain actual flow m
FW(2) m that obtains according to step (1)
FWDetermine that water changes the required thermal power P of steam into
W(3) determine the thermal power P that reactor-loop produces
S(4) determine water mismatching amount of steam (P
W-P
S).
Feedwater flow m in the step (1)
FWMAdopt orifice flowmeter to measure.
Actual feedwater flow m in the step (1)
FW, obtain by following formula:
Wherein: m
FWM---be the feedwater flow that measures, kg/s;
m
FW---be the actual feedwater flow after overcorrect, kg/s;
T
FW---actual feed temperature, K;
Water changes the required thermal power P of steam in the step (2)
W, obtain by following formula:
Wherein: P
w-water changes the required percentage power of steam, % into;
m
FW---the actual feedwater flow after overcorrect, kg/s;
K---constant, 0.1844;
T
FW---actual feed temperature, K;
The thermal power P that reactor-loop produces in the step (3)
S, obtain by following formula:
P
s=(N+0.167×n)
Wherein: P
s---the percentage power that reactor-loop produces, %;
N---reactor percentage power, %;
N---operation main pump quantity;
Beneficial effect of the present invention: (1) has proofreaied and correct the actual feedwater flow of steam generator, changing the flow water mismatching amount of steam is the thermal power amount of mismatch, it is inaccurate so fundamentally to have avoided steam to change the flow measurement that causes by temperature, pressure, reduce measuring error, improved the security and the reliability of nuclear power station; (2) whole measuring method practical operation is only to need accurately to measure feedwater flow m
FWMAnd temperature T
FWGet final product, need measurement parameter few, easy to operate, accuracy and feasibility height.
Embodiment
Describe this measuring method in detail below in conjunction with specific embodiment.
A kind of measuring method of steam-water mismatching amount of steam generator, it may further comprise the steps:
(1) measures the feed temperature T that enters steam generator
FWWith feedwater flow m
FWM, obtain actual flow m
FW
Measure feedwater flow m with orifice flowmeter
FWM, read actual feed temperature T by thermometric instrument
FWCalculate actual feedwater flow m according to formula as (1)
FW
Then
Wherein: m
FWM---be the feedwater flow that measures, kg/s;
m
FW---be the actual feedwater flow after overcorrect, kg/s;
T
FW---actual feed temperature, K;
(2) determine that water changes the required thermal power P of steam into
W
Water changes the required thermal power P of steam into
WCan have following formula to calculate:
Wherein: P
W---water changes the required percentage power of steam, % into;
m
FW---the actual feedwater flow after overcorrect, kg/s;
K---constant, 0.1844;
T
FW---actual feed temperature, K;
(3) determine the thermal power P that reactor-loop produces
S
The thermal power that a heat output of reactor and a loop main pump operation produce passes to the secondary circuit medium through steam generator, is secondary circuit master feedwater and becomes the obtainable heat of steam.
P
s=(N+0.167×n)(3)
Wherein, N---this nuclear power plant reactor percentage power, 99%;
N---operation main pump quantity, 4;
(4) determine water mismatching amount of steam (P
W-P
S)
Last water mismatching amount of steam calculates and shows as (P
W-P
S), P wherein
WFor arriving, actual feedwater flow temperature produces steam desired power, P
SBe the power that a loop can produce.If (P
W-P
S) be negative, the heat of then representing a loop to produce is too much, quantity of steam has the risk that causes the steam generator liquid level to reduce greater than feedwater in the steam generator, reach a threshold value after, need to trigger automatic function as reducing a power loop.Like this, just can calculate water mismatching amount of steam by power, steam generator master feed temperature pressure, flow, steam generator pressure inside that measurement enters steam generator.
Under the current set state, 222 ℃ of main feed temperatures, flow 410 * 4 Kilograms Per Seconds become the required thermal power P of saturated-vapor state according to what formula (2) was calculated
WBe 99.4%, calculating the power that a loop can produce according to formula (3) is 99.5%, water mismatching amount of steam (P
W-P
S) be-0.1%.
Claims (5)
1. the measuring method of a steam-water mismatching amount of steam generator is characterized in that, this method comprises set by step following: (1) measures the feed temperature T that enters steam generator
FWWith feedwater flow m
FWM, obtain actual flow m
FW(2) m that obtains according to step (1)
FWDetermine that water changes the required thermal power P of steam into
W(3) determine the thermal power P that reactor-loop produces
S(4) determine water mismatching amount of steam (P
W-P
S).
2. the measuring method of a kind of steam-water mismatching amount of steam generator according to claim 1 is characterized in that, the feedwater flow m in the step (1)
FWMAdopt orifice flowmeter to measure.
3. the measuring method of a kind of steam-water mismatching amount of steam generator according to claim 1 and 2 is characterized in that, the actual feedwater flow m in the step (1)
FW, obtain by following formula:
Wherein: m
FWM---be the feedwater flow that measures, kg/s;
m
FW---be the actual feedwater flow after overcorrect, kg/s;
T
FW---actual feed temperature, K.
4. the measuring method of a kind of steam-water mismatching amount of steam generator according to claim 3 is characterized in that, water changes the required thermal power P of steam in the step (2)
W, obtain by following formula:
Wherein: P
W---water changes the required percentage power of steam, % into;
m
FW---the actual feedwater flow after overcorrect, kg/s;
K---constant, 0.1844;
T
FW---actual feed temperature, K.
5. the measuring method of a kind of steam-water mismatching amount of steam generator according to claim 1 is characterized in that, the thermal power P that reactor-loop produces in the step (3)
S, obtain by following formula:
P
s=(N+0.167×n)
Wherein: P
s---the percentage power that reactor-loop produces, %;
N---reactor percentage power, %;
N---operation main pump quantity.
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CN2009101193903A CN101846535B (en) | 2009-03-25 | 2009-03-25 | Method for measuring steam-water mismatching amount of steam generator |
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CN2009101193903A CN101846535B (en) | 2009-03-25 | 2009-03-25 | Method for measuring steam-water mismatching amount of steam generator |
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CN101846535A true CN101846535A (en) | 2010-09-29 |
CN101846535B CN101846535B (en) | 2011-12-28 |
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Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103808433A (en) * | 2012-11-14 | 2014-05-21 | 中国广东核电集团有限公司 | Nuclear power station thermal power measurement drift monitoring method |
CN104332193A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Steam-generator water-level measure method based on digitization technology |
CN111166155A (en) * | 2018-11-12 | 2020-05-19 | 九阳股份有限公司 | Cooking control method of steam heating type cooking appliance |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5237816A (en) * | 1983-05-23 | 1993-08-24 | Solar Turbines Incorporated | Steam generator control systems |
CN1118831C (en) * | 2000-06-21 | 2003-08-20 | 北京和利时***工程股份有限公司 | Method for measuring power of pressurized-water reactor core for nuclear power station |
US7040095B1 (en) * | 2004-09-13 | 2006-05-09 | Lang Fred D | Method and apparatus for controlling the final feedwater temperature of a regenerative rankine cycle |
CN1680787A (en) * | 2004-11-22 | 2005-10-12 | 北京山鑫海达科技发展有限公司 | Thermal diffusion heat flowmeter, thermal flowmeter and measuring method thereof |
-
2009
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103808433A (en) * | 2012-11-14 | 2014-05-21 | 中国广东核电集团有限公司 | Nuclear power station thermal power measurement drift monitoring method |
CN103808433B (en) * | 2012-11-14 | 2017-12-26 | 中国广核集团有限公司 | The monitoring method of nuclear power station thermal power measurement drift |
CN104332193A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Steam-generator water-level measure method based on digitization technology |
CN104332193B (en) * | 2013-07-22 | 2016-12-28 | 中国核动力研究设计院 | A kind of steam generator water level measuring method based on digitizing technique |
CN111166155A (en) * | 2018-11-12 | 2020-05-19 | 九阳股份有限公司 | Cooking control method of steam heating type cooking appliance |
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